PROCESSING PROCEDURES OF NEUTRONIC CHARACTERISTICS IN CFC_BN (PREPRINT IBRAE-2013-05)

Preprint IBRAE-2013-05

Mitenkova E., Solovieva E.

Processing procedures of neutronic characteristics in CFC_BN are intended for balance analysis of accumulation of actinides and fission products in burn-up calculation using MCNP5MONTEBURNS1.0ORIGEN2. They include the special procedures for express analysis of large output data sets. The program CFC_BN is designed for fuel cycle simulation using MCNP5MONTEBURNS1.0ORIGEN2.

Bibliographical reference

Mitenkova E. Processing procedures of neutronic characteristics in CFC_BN — (Preprint / Nuclear Safety Institute RAS, October 2013, № IBRAE-2013-05). — Moscow : NSI RAS, 2013. — 19 p. — Bibliogr.: 8 items.